Validation of Three-Dimensional Synthesis RPV Neutron Fluence Calculations Using VVER-1000 Ex-Vessel Reference Dosimetry Results
According to Russian federal norms and the safety guide of the nuclear regulatory body of Russia, the maximum fast neutron fluence above 0.5 MeV at critical positions of the reactor pressure vessel (RPV) of VVER-type reactors is used for prediction of the RPV lifetime. For the computation of neutron fluences in the RPV near the reactor core midplane level, the three-dimensional (3-D) synthesis method based on two- and one-dimensional S{sub N} calculations may be acceptable but needs validation. The present validation analysis was carried out on the basis of neutron transport calculations for a VVER-1000 model by means of the well-known codes DORT (R, {Theta}- and R, Z geometry) and ANISN (R geometry) using the multigroup library BUGLE-96. The 3-D spatial neutron source distribution, including pin-to-pin power variations and the complex baffle construction, were modeled in detail.
- Research Organization:
- Gosatomnadzor of Russia, Moscow (RU); Forschungszentrum Rossendorf e.V., Dresden (DE)
- Sponsoring Organization:
- none (US)
- OSTI ID:
- 786257
- Report Number(s):
- ISSN 0003-018X; CODEN TANSAO; ISSN 0003-018X; CODEN TANSAO; TRN: US0109315
- Resource Relation:
- Conference: 2000 Annual Meeting, San Diego, CA (US), 06/04/2000--06/08/2000; Other Information: Transactions of the American Nuclear Society, Volume 82; PBD: 4 Jun 2000
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
DOSIMETRY
FAST NEUTRONS
NEUTRON FLUENCE
PRESSURE VESSELS
REACTOR CORES
VALIDATION
WWER-5 REACTOR
SERVICE LIFE
D CODES
A CODES
THREE-DIMENSIONAL CALCULATIONS
ONE-DIMENSIONAL CALCULATIONS
TWO-DIMENSIONAL CALCULATIONS
MATHEMATICAL MODELS
COMPUTER CALCULATIONS
COMPUTERIZED SIMULATION
B CODES